Irradiation test using foreign reactor, 1; Study of irradiation test with capsule temperature control system (Joint research)

Takabe, Yugo; Otsuka, Noriaki; Fuyushima, Takumi; Sayato, Natsuki; Inoue, Shuichi; Morita, Hisashi; Jaroszewicz, J.*; Migdal, M.*; Onuma, Yuichi; Tobita, Masahiro*; et al.

JAEA-Technology 2022-040, 45 Pages, 2023/03

JAEA-Technology-2022-040.pdf:6.61MB

Because of the decommission of the Japan Materials Testing Reactor (JMTR), the domestic neutron irradiation facility, which had played a central role in the development of innovative nuclear reactors and the development of technologies to further improve the safety, reliability, and efficiency of light water reactors, was lost. Therefore, it has become difficult to pass on the operation techniques of the irradiation test reactors and irradiation technologies, and to train human resources. In order to cope with these issues, we conducted a study on the implementation of irradiation tests using overseas reactors as neutron irradiation sites as an alternative method. Based on the "Arrangement between the National Centre for Nuclear Research and the Japan Atomic Energy Agency for Cooperation in Research and Development on Testing Reactor," the feasibility of conducting an irradiation test at the MARIA reactor (30 MW) owned by the National Centre for Nuclear Research (NCBJ) using the temperature control system, which is one of the JMTR irradiation technologies, was examined. As a result, it was found that the irradiation test was possible by modifying the ready-made capsule manufactured in accordance with the design and manufacturing standards of the JMTR. After the modification, a penetration test, an insulation continuity test, and an operation test in the range of room temperature to 300C, which is the operating temperature of the capsule, were conducted and favorable results were obtained. We have completed the preparations prior to transport to the MARIA reactor.

Test program for reactor control system in rise-to-power test in HTTR

Nakagawa, Shigeaki; Saito, Kenji; Homma, Fumitaka; Tachibana, Yukio; Kunitomi, Kazuhiko

JAERI-Tech 2000-009, p.88 - 0, 2000/02

JAERI-Tech-2000-009.pdf:6.19MB

no abstracts in English

Reactor Engineering Department annual report; April 1, 1997 - March 31, 1998

JAERI-Review 98-022, 265 Pages, 1998/11

JAERI-Review-98-022.pdf:12.29MB

no abstracts in English

Advantage of modified JAERI passive safety reactor (JPSR-II)

Murao, Yoshio; Ochiai, Masaaki

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00

no abstracts in English

Design and present status of high-temperature engineering test reactor

Baba, Osamu; Kunitomi, Kazuhiko; Kawaji, Satoshi; Tanaka, Toshiyuki; Shiozawa, Shusaku; Okubo, Minoru

Proc. of ASMEJSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 2, p.281 - 287, 1996/00

no abstracts in English

Air monitoring and control in nuclear facilities

Ikezawa, Yoshio

Kurin Tekunoroji, 3(4), p.41 - 45, 1993/04

no abstracts in English

SHETEMP: A Computer code for calculation of fuel temperature behavior under reactivity initiated accidents

Araya, Fumimasa;

JAERI-M 91-071, 53 Pages, 1991/05

JAERI-M-91-071.pdf:1.26MB

no abstracts in English

A Feasibility study on the innovative control rod driving mechanism, 1

Ishizaka, Yuichi*;

JAERI-M 89-174, 105 Pages, 1989/11

JAERI-M-89-174.pdf:9.76MB

no abstracts in English

Safety Analysis on the Operational Transients and some Accidents of MUTSU Reactor

;

JAERI-M 9398, 147 Pages, 1981/03

JAERI-M-9398.pdf:3.1MB

no abstracts in English